Integration of Physical Security Simulation Software Applications in a Dynamic Risk Framework, INL/EXT-21-64333 | 221385 | | Integration of Physical Security Simulation Software Applications in a Dynamic Risk Framework, INL/EXT-21-64333 | Integration of Physical Security Simulation Software Applications in a Dynamic Risk Framework, INL/EXT-21-64333 | | 9/8/2021 5:20:28 PM | INL/EXT-21-64333 Revision 0 Light Water Reactor Sustainability Program Integration of Physical Security Simulation Software Applications in a Dynamic Risk Framework August 2021 | 69 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
Methodology and Application of Physical Security Effectiveness Based on Dynamic Force-on-Force Modeling, INL/EXT-20-59891 | 221259 | | Methodology and Application of Physical Security Effectiveness Based on Dynamic Force-on-Force Modeling, INL/EXT-20-59891 | Methodology and Application of Physical Security Effectiveness Based on Dynamic Force-on-Force Modeling, INL/EXT-20-59891 | | 9/30/2020 9:58:38 PM | INL/EXT-20-59891 Light Water Reactor Sustainability Program Methodology and Application of Physical Security Effectiveness Based on Dynamic Force-on-Force Modeling September 2020 | 49 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
Integration of FLEX Equipment and Operator Actions in Plant Force-On-Force Models with Dynamic Risk Assessment, INL/EXT-20-59510 | 221382 | | Integration of FLEX Equipment and Operator Actions in Plant Force-On-Force Models with Dynamic Risk Assessment, INL/EXT-20-59510 | Integration of FLEX Equipment and Operator Actions in Plant Force-On-Force Models with Dynamic Risk Assessment, INL/EXT-20-59510 | | 8/27/2020 1:15:47 AM | U.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government Labor costs continue to rise in | 49 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
Status of Adaptive Surrogates within the RAVEN Framework, INL/EXT-17-43438 | 269299 | | The RAVEN code has been under development at the Idaho National Laboratory since 2012. Its main goal is to create a multi-purpose platform for the deploying of all the capabilities needed for Probabilistic Risk Assessment, uncertainty quantification, data mining analysis and optimization studies. | The RAVEN code has been under development at the Idaho National Laboratory since 2012. Its main goal is to create a multi-purpose platform for the deploying of all the capabilities needed for Probabilistic Risk Assessment, uncertainty quantification, data mining analysis and optimization studies. | | 11/6/2017 9:29:14 PM | INL/EXT-17-43438 Light Water Reactor Sustainability Program Status of Adaptive Surrogates within the RAVEN framework Andrea Alfonsi, Congjian Wang, Joshua Cogliati, Diego | 7 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
A Simulation Based Dynamic Analysis Approach for Modeling Total Plant Response to Flooding Events, INL/EXT-17-40928 | 221400 | | A Simulation-Based Dynamic Analysis Approach for Modeling Total Plant Response to Flooding Events, RIL 2022-03 INL/EXT-17 40928 | A Simulation-Based Dynamic Analysis Approach for Modeling Total Plant Response to Flooding Events, RIL 2022-03 INL/EXT-17 40928 | | 4/29/2022 4:04:31 PM | Research Information Letter Office of Nuclear Regulatory Research This report was prepared as Idaho National Laboratory Report | 24 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
System Reliability Analysis Capability and Surrogate Model Application in RAVEN, INL/EXT-16-37243 | 269300 | | This report describes the effort performed to improve the analysis capabilities of the RAVEN code. These efforts include improving the reliability (or “limit”) surface search of the RAVEN code and exploring new opportunities in usage of surrogate models by extending the current RAVEN capabilities to multi-physics surrogate models construction for high-dimensionality problems. | This report describes the effort performed to improve the analysis capabilities of the RAVEN code. These efforts include improving the reliability (or “limit”) surface search of the RAVEN code and exploring new opportunities in usage of surrogate models by extending the current RAVEN capabilities to multi-physics surrogate models construction for high-dimensionality problems. | | 7/27/2017 8:30:18 PM | INL/EXT-16-37243 Light Water Reactor Sustainability Program System Reliability Analysis Capability and Surrogate Model Application in RAVEN Cristian Rabiti, Andrea Alfonsi | 5 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
Risk-Informed Safety Margin Characterization Methods Development Work, INL/EXT-14-33191 | 269301 | | This report presents several analyses that demonstrate the value of the RISMC approach in order to assess risk associated with nuclear power plants (NPPs). We focus on simulation-based PRA which, in contrast to classical PRA, heavily employs system simulator codes. First, we compare, these two types of analyses, classical and RISMC, for a Boiling Water Reactor (BWR) Station Black Out (SBO) initiating event. | This report presents several analyses that demonstrate the value of the RISMC approach in order to assess risk associated with nuclear power plants (NPPs). We focus on simulation-based PRA which, in contrast to classical PRA, heavily employs system simulator codes. First, we compare, these two types of analyses, classical and RISMC, for a Boiling Water Reactor (BWR) Station Black Out (SBO) initiating event. | | 9/30/2014 9:34:17 PM | INL/EXT-14-33191 Light Water Reactor Sustainability Program Risk-Informed Safety Margin Characterization Methods Development Work September 2014 DOE Office of Nuclear Energy | 10 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
Advanced probabilistic risk analysis using RAVEN and RELAP-7, INL/EXT-14-32491 | 269302 | | Advanced probabilistic risk analysis using RAVEN and RELAP-7, INL/EXT-14-32491 | Advanced probabilistic risk analysis using RAVEN and RELAP-7, INL/EXT-14-32491 | | 8/17/2015 8:43:08 PM | 7KH,1/LVD86'HSDUWPHQWRI(QHUJ\1DWLRQDO/DERUDWRU\ RSHUDWHGE\%DWWHOOH(QHUJ\$OOLDQFH ,1/(;7 Advanced Probabilistic Risk Analysis Using RAVEN and RELAP-7 | 5 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
Support and Modeling for the Boiling Water Reactor Station Black Out Case Study Using RELAP and RAVEN, INL/EXT-13-30203 | 269303 | | The existing fleet of nuclear power plants is in the process of extending its lifetime and increasing the power generated from these plants via power uprates. In order to evaluate the impact of these two factors on the safety of the plant, the RISMC project aims to provide insight to decision-makers through a series of simulations of the plant dynamics for different initial conditions. | The existing fleet of nuclear power plants is in the process of extending its lifetime and increasing the power generated from these plants via power uprates. In order to evaluate the impact of these two factors on the safety of the plant, the RISMC project aims to provide insight to decision-makers through a series of simulations of the plant dynamics for different initial conditions. | | 12/20/2013 4:26:24 PM | The INL is a U.S. Department of Energy National Laboratory operated by Battelle Energy Alliance INL/EXT-13-30203 Light Water Reactor Sustainability Program Support and Modeling | 12 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
Reactor analysis and virtual control environment (RAVEN) FY12, INL/EXT-12-27351 | 269304 | | RAVEN is a complex software tool that has functionality spanning from being the RELAP-7 user interface, to using RELAP-7 to perform Risk Informed Safety Characterization (RISMC), and to controlling RELAP-7 calculation execution. | RAVEN is a complex software tool that has functionality spanning from being the RELAP-7 user interface, to using RELAP-7 to perform Risk Informed Safety Characterization (RISMC), and to controlling RELAP-7 calculation execution. | | 10/8/2012 9:42:12 PM | The INL is a U.S. Department of Energy National Laboratory operated by Battelle Energy Alliance INL/EXT-12-27351 Reactor Analysis and Virtual Control Environment (RAVEN) FY12 | 8 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |